Circulating and plateout activity program for gas-cooled reactors with arbitrary radioactive chains
A time-dependent method for estimating the fuel body, circulating, plateout, and filter inventory of a high temperature gas-cooled reactor (HTGR) during normal operation is discussed. The primary coolant model accounts for the source, buildup, decay, and cleanup of isotopes that are gas borne inside the prestressed concrete reactor vessel (PCRV). This method has been implemented in the SUVIUS computer program that is described in detail.
- Research Organization:
- Los Alamos Scientific Lab., NM (USA)
- DOE Contract Number:
- W-7405-ENG-36
- OSTI ID:
- 7011527
- Report Number(s):
- LA-7239-MS; NUREG/CR-0060
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTIVITY LEVELS
COMPUTER CODES
COOLING SYSTEMS
DEPOSITION
FISSION PRODUCTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
RADIOACTIVE MATERIALS
RADIOACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
S CODES
210300* -- Power Reactors
Nonbreeding
Graphite Moderated
ACTIVITY LEVELS
COMPUTER CODES
COOLING SYSTEMS
DEPOSITION
FISSION PRODUCTS
GAS COOLED REACTORS
GRAPHITE MODERATED REACTORS
HTGR TYPE REACTORS
ISOTOPES
MATHEMATICAL MODELS
PRIMARY COOLANT CIRCUITS
RADIOACTIVE MATERIALS
RADIOACTIVITY
REACTOR COMPONENTS
REACTOR COOLING SYSTEMS
REACTORS
S CODES